Suppression Method of Radionuclide Deposition on Reactor Component of Nuclear Power Plant and Ferrite Film Formation Apparatus

ABSTRACT

A method of suppressing deposition of radionuclides on components of a nuclear power plant comprises forming a ferrite film by contacting a first chemical including iron (II) ions, a second chemical for oxidizing the iron (II) ions to iron (III) ions, and a third chemical for adjusting the pH of a processing solution containing a mixture of the first and second chemicals to be 5.5 to 9.0 with the metal member surface in a time period from a finishing stage in decontamination step of removing contaminants formed on the surface of metal member composing the nuclear power plant, and suppressing deposition of radionuclides on the metal member by the ferrite film.

CROSS REFERENCE TO RELATED APPLICATION

This application is a continuing application of U.S. application Ser.No. 11/181,809, filed Jul. 15, 2005, which claims priority under 35U.S.C. §119 to Japanese Patent Application No. 2004-214541, filed Jul.22, 2004, the entire disclosure of which are herein expresslyincorporated by reference.

BACKGROUND OF THE INVENTION

1. Field of the Invention

The present invention relates to a method of suppressing deposition ofradionuclides on components of a power plant such as a nuclear powerplant, and a ferrite film formation apparatus for performing theradionuclide deposition suppression method.

2. Background Arts

For example, in a nuclear power plant of boiling water type reactor(hereunder abbreviated as BWR), the heat generated by fuel iseffectively transferred to cooling water by forcibly circulating thecooling water by a primary loop recirculation pump and internal pumpsinside the nuclear reactor comprising a reactor pressure vessel andcontrol rods contained therein. Most of the steam generated from thecooling water in this way is used for driving a steam turbine generator,the steam exhausted from the steam turbine is condensed in a condenser,and the condensate condensed in the condenser is almost fully deaeratedand supplied again as cooling water of the nuclear reactor. In thiscase, in the condenser, oxygen and hydrogen generated by decompositionof water by radiation are also almost completely removed. Further, thecondensate to be returned to the nuclear reactor is supplied to thenuclear reactor after removing mainly metal impurities by anion-exchange resin filter and being heated to nearly 200° C., in orderto suppress occurrence of activated corrosive products in the nuclearreactor.

Further, since the activated corrosive products are generated inside therector pressure vessel and at water-contact portions of a recirculationsystem, stainless steel such as nickel-base metal which is less incorrosion is used for components of the main primary system. Further,for a reactor pressure vessel made of low alloy steel, inside buildingup of stainless steel is performed, thereby to prevent the low alloysteel from contacting directly with the reactor water. In addition totaking into a consideration the above-mentioned matters, a part of thereactor water is purified by a reactor-water cleanup facility and metalimpurities produced slightly in the reactor water are positivelyremoved.

However, even if the above-mentioned measures for corrosion preventionare taken, very slight metal impurities exist inevitably in the reactorwater, so that a part of the metal impurities deposits on the surface ofa fuel rod as metal oxide. Metal elements deposited on the surface ofthe fuel rod are irradiated by neutrons radiated from the fuel to causenuclear reaction, whereby radionuclides such as cobalt 60, cobalt 58,chromium 51, manganese 54, etc are produced. Most of those radionuclidesare, as they are, deposited on the fuel rod surface in a state of oxide,however, a part of the radionuclides is solved out into the coolingwater according to the solubility of oxides taken in and released againinto the reactor water as insoluble solid called cruds. Radioactivesubstances in the reactor water are removed by a reactor-water purifyingsystem, however, radioactive substances that can not be removed areaccumulated on surfaces of water-contact portions of the componentswhile the substances are recirculating in a recirculation system and soon together with the reactor water. As a result, radiations are radiatedfrom the surface of the components, which becomes a cause of radiationexposure on person engaged with regular inspection during theinspection. A dose of radiation exposure under working is managed not toexceed a specified value for each person, however, recently thespecified value is raised and there occurs the necessity that theexposure dose for each person is reduced as low as economicallypossible.

Therefore, various methods such as a method of reducing deposition ofradionuclides on piping, a method of reducing the concentration ofradionuclides in the reactor water, etc. are studied. For example, thereis proposed a method of injecting metal ions such as zinc into thereactor water, forming a dense oxide film including zinc on thewater-contact surface of piping of a recirculation system andsuppressing to take radionuclides such as cobalt 60, cobalt 58, etc.into the oxide film (Patent literature 1). Further, there is proposed amethod of forming a pre-oxidation film under a certain condition oninner surfaces of recirculation system piping and a reactor-waterpurifying system in which the reactor water flows during operation,before reaching to the condition that the radionuclides are solved outor released (Patent literature 2).

Patent literature 1: JP 58-79196 A

Patent literature 2: JP 62-95498 A

DISCLOSURE OF THE INVENTION Subject to be Solved by the Invention

The method of injecting metal ions such as zinc into the reactor wateras described in Patent literature 1 has a problem that depleted zincmust be used to avoid zinc itself being radioactivated, in addition tothe problem that injection of zinc ions must be always continued duringoperation.

Further, since the method of forming an oxide film described in Patentliterature 2 forms the oxide film in an operation-temperature range(250˜300° C.) of BWR, for instance, it is found that there are followingproblems: Namely, according to the study of the inventors, it is foundthat in the case where material of components to be formed of oxide filmis stainless steel, inner oxide film having much chromium component isformed first on the surface of component, and an outer oxide film havingless chromium component is formed on the inner oxide film surface.Particularly, in the case of such a double layer structure oxide film,it has such a property that radioactive Co-60 and Co-58 are easily takenin the inner oxide film, and it is found that a suppression effect ofradioactive nuclide deposition is not so large.

It is an object of the present invention to effectively suppressdeposition of radionuclides on components of a nuclear power plant.

Means for Solving the Above Subject

In order to solve the above subject or achieve the above object, variousstudies are conducted, as a result, the following is found.

First, when an oxide film is formed in a high temperature atmospheresuch as a reactor water temperature range (for example 250˜300° C.)during service operation, the diffusion velocity of oxygen generated byradiolysis of water into metal parent material of a component that theoxide film is to be formed, and oxidation velocity of parent material isfast, so that the oxide film (inner layer) formed initially becomes muchin chromium component contained in stainless steel.

Secondly, a main component of the oxide film (outer layer) formed on theinner oxide film is iron because iron ions dissolved out from the parentmaterial precipitate in high temperature water beyond the solubility.

Thirdly, when an oxide film is formed in a high-temperature atmospheresuch as in a temperature range during service operation, a filmstructure such as crystal of the outer oxide film formed on the inneroxide film is not always densely formed. Therefore, radionuclides suchas cobalt in the reactor water transmit the outer oxide film, and theradionuclides are taken in the inner oxide film in the form that theyare replaced by ion components in the inner oxide film.

The experiments conducted by the inventors to get such knowledge areexplained, referring to FIGS. 2 to 4. FIG. 2 shows an experimentalresult about stainless steel in which oxide film is not formed inadvance, the experimental result being a deposit amount of Co-58deposited on a sample, obtained with time passage, by soaking the samplein cooling water under the condition of service operation of BWR. InFIG. 2, the abscissa shows soaking time and the ordinate shows relativevalues of Co-58 deposit. As shown in FIG. 2, such a tendency is shownthat Co-58 deposit increases with passage of soaking time and finallythe deposit saturates. This change in Co-58 deposition has a tendencysimilar to the tendency of oxide film growth. That is, a corrosion rateis fast at an initial time of soaking and a deposition rate of Co-58also becomes fast because the film growth rate is fast. However, afterpassage of about 500 hours, the CO-58 deposition rate becomes slow asthe film growth rate becomes slow by diffusion resistance of anoxidizing agent in high temperature water due to the grown oxide film.

FIG. 3 shows an experimental result that a sample A that a pre-oxidationfilm is not formed on stainless steel and a sample B that apre-oxidation film is formed on stainless steel are soaked in thecooling water under the condition of BWR service operation and relativevalues of deposit of Co-58 deposited on the samples A and B arecompared. In those samples A and B, A1 and B1 each are an inner oxidefilm that chromium is a main component, and A2 and B2 are each are anouter oxide film that iron is a main component. From this experimentalresult, it is found that radioactive cobalt is taken in the inner oxidefilm B of chromium of a main component in the case of pre-oxidation filmformed in the high temperature water under the condition of BWR serviceoperation as in the sample B. That is, it is found that a depositionsuppression effect of radionuclides is small even if it is tried tosuppress taking in of cobalt by forming the pre-oxidation film in thehigh temperature water under the condition of BWR service operation andmaking the growth rate of the oxide film formed during the serviceoperation slow. On the contrary, in the case of the sample A that thepre-oxidation film is not formed, it appears that taking in of cobalt iseasily occurs in the course of growing of the outer oxide film A2 thatiron is a main component. However, by providing the pre-oxidation filmas in the sample B, it is found that it becomes difficult to take cobaltinto the outer oxide film B2 becoming slow in growth. It is found thatthe outer oxide films A2 and B2 that iron is a main component areferrite films (hereunder, referred to as magnetite films) that magnetiteis a main component from analysis of laser Raman spectral. From theabove-mentioned matters, if it is possible to produce a magnetite filmas an oxide film, it is expected to be able to suppress deposition ofcobalt.

However, when forming an oxide film in a water of high temperature closeto a temperature in a BWR service operation, since it is impossible tosuppress having formed an inner oxide film B1 that chromium is a maincomponent through diffusion of dissolved oxygen in the cooling waterinto the metal parent material, such a problem is left that the inneroxide film B1 becomes a source of taking in radioactive cobalt and it isimpossible to suppress deposition of radionuclides.

If it is possible to form only a magnetite film such as the outer oxidefilm A2, B2 under the temperature condition (for example, 100° C. orlower) that the diffusion rate of dissolved oxygen into metal parentmaterial is slow, it is considered to be able to suppress taking in ofcobalt of radionuclides.

After forming a magnetite film on a stainless steel surface on the basisof this consideration, it is soaked in the high-temperature water underthe condition of BWR service operation and a deposit amount of Co-60 isexamined. As a result, it is found possible to suppress greatly thedeposit amount of Co as sown in FIG. 4. In FIG. 4, the ordinate showsrelative values of deposit of Co-58 of samples C, D, E. The sample C isa sample that a surface of stainless steel is mechanically grinded, thesample D is a sample that a pre-oxidation film is formed on the surfaceof stainless steel under the condition of BWR service operation, and thesample E is a sample that a magnetite film is formed on the surface ofstainless steel at a temperature of 100° C. or less. As it is apparentfrom FIG. 4, the deposit amount of Co in the sample E in which themagnetite film is formed is greatly suppressed as compared with thesamples C and D. Further, as a method of forming the magnetite film, itis not technique of suppressing corrosion of components of a nuclearpower plant, but it is technique of forming a ferrite film of magneticrecording medium. However, a method described in JP 63-15990 B can beapplied for the method, for instance. Although the method of JP 63-15990B uses chlorine, however, it is impossible for the components of nuclearpower plant to use chlorine from a viewpoint of securing of soundness ofthe components, so that it is necessary to take a method different fromthe method of JP 63-15990 B.

The present invention is made to solve the above-mentioned subject andcharacterized by adsorbing iron (II) ions (ferrous ions) on surfaces ofmetal members composing a nuclear power plant, oxidizing the adsorbediron (II) ions to form ferrite films under the temperature conditionfrom a normal temperature to 200° C., preferably from a normaltemperature to 100° C., more preferably from 60° C. to 100° C., andsuppressing deposition of radionuclides on the metal members by theferrite films, on the basis of the acknowledge.

According to the above, the ferrite films formed on the surfaces ofmembers composing a nuclear power plant are ferrite films that magnetiteis a main component, corresponding to the sample E in FIG. 4, becausethe temperature at time of forming the films is lower than thetemperature in the core service operation. That is, in the case wherethe temperature at time of ferrite film formation is in a temperaturerange at time of service operation of the core, since a diffusionvelocity of an oxidizing agent (oxidizer) is fast, a conventional inneroxide film that chromium is a main component is formed, and cobalt istaken in there. On the contrary, in the case where the temperature attime of formation of the ferrite film is 60° C. to 100° C. which is low,since the diffusion velocity of the oxidizer is slow, the conventionalinner oxide film that chromium is a main component is not formed, but amagnetite film that taking in of radionuclides is less and iron is amain component, corresponding to the sample E in FIG. 4 is formed,whereby it is possible to suppress deposition of radionuclides ontocomponents.

Further, after acting a solution including bivalent iron ion (iron (II)ion) obtained by solving iron in organic acid or carbonic acid onto thesurfaces of components, an oxidizer such as oxygen is injected into thesolution, whereby it is possible to form the oxide film.

When the radionuclide deposition suppression method according to thepresent invention is applied, it is preferable for a water-contactsurface of a component to be treated to be bare (to have nothingthereon). Particularly, on the surfaces of components having operatedfor service, oxide films for corrosion prevention are formed by oxygenof an oxidizer produced by radiolysis of water in the cooling water. Theoxide film has been formed in a high-temperature range under serviceoperation, so that the oxide film that chromium is a main component hasbeen formed as in the inner oxide film B1 of the sample B in FIG. 3, andradionuclides have been already taken in. Therefore, even if a magnetitefilm according to the present invention is formed on the oxide film, itis impossible to obtain a sufficient exposure-dose reducing effectthereby.

Therefore, the radionuclide deposition suppression method according tothe present invention is preferable to be practiced after termination ofa decontamination process such as chemical decontamination and so onconducted commonly in the nuclear power plant. Concretely, it ispreferable to practice the method after a termination stage of thedecontamination process and before starting the core. That is, thedecontamination such as chemical decontamination or the like is atreatment for removing radionuclides deposited on the surfaces ofnuclear power plant components in contact with reactor water togetherwith oxide films. Therefore, the radionuclide deposition suppressionmethod according to the present invention is practiced under thecondition that surfaces of parent material of components to be treatedare exposed by the decontamination, and any natural oxide film doesalmost not exist. As a result, a magnetite film which is a kind offerrite film according to the present invention is formed directly onthe surface of component, so that it is possible to effectively suppressdeposition of radionuclides. Thereby, it is possible to reduce exposuredose at time of regular inspection working.

As components or members that the radionuclide deposition suppressionmethod according to the present invention is applied, components ormembers composing a reactor-water recirculation system or reactor-waterpurifying system of a BWR power plant are preferable, but the componentor members are not limited thereto. Further, the present invention isnot limited to the BWR plant, but it can be applied for suppressiontechnique of radionuclides deposition on components in contact withreactor water in a pressurized water type (PWR) nuclear power plant.

A ferrite film forming apparatus for practicing the radionuclidedeposition suppression method according to the present inventioncomprises a surge tank for storing a processing solution, arecirculation pump for sucking the processing solution in the surgetank, processing solution supply piping for supplying the processingsolution sucked by the recirculation pump to piping for film formation,a first chemical tank for storing iron (II) ions to be injected into theprocessing solution in the processing solution supply piping, a secondchemical tank for storing an oxidizer to be injected into the processingsolution in the processing solution supply pipe, a third chemical tankfor storing a pH adjuster to adjusting the pH of the processing solutionin the processing solution supply piping to be 5.5 to 9.0, a processingsolution return piping for returning the processing solution to bereturned from the piping for film formation to the surge tank, and aheater for heating the processing solution to a temperature of 60-100°C.

Further, when the apparatus is used both as film formation and aschemical decontamination, it is possible to construct the apparatus soas to fluidly communicate a chemical tank for oxidizer and reducer forchemical decontamination of the piping that a film is to be formed tothe above-mentioned processing solution supply piping.

EFFECT OF THE INVENTION

According to the present invention, it is possible to effectivelysuppress deposition of radionuclides on components of a nuclear powerplant.

BRIEF DESCRIPTION OF THE DRAWINGS

FIG. 1 is a flow chart of an embodiment of a radionuclide depositionsuppression method of the present invention;

FIG. 2 is a graph showing an experimental result about stainless steelin which pre-oxidation film is not formed, the experimental result beingdeposit of Co-58 deposited on a sample, obtained with time passage, bysoaking the sample in cooling water under the condition of serviceoperation of BWR;

FIG. 3 is a graph showing an experimental result that a sample A that apre-oxidation film is not formed on stainless steel and a sample B thata pre-oxidation film is formed on stainless steel are soaked in thecooling water under the condition of BWR service operation and relativevalues of deposit of Co-58 deposited on the samples A and B arecompared;

FIG. 4 is a graph showing an experimental result that after forming amagnetite film on a stainless steel surface, it is soaked in thehigh-temperature water under the condition of BWR service operation anddeposit of Co-60 is examined;

FIG. 5 is a schematic diagram of a whole system construction of anembodiment in which the present invention is applied to recirculationpiping of a nuclear power plant;

FIG. 6 is a schematic diagram of a detailed system construction of afilm forming apparatus for practicing the radionuclide depositionsuppression method according to the present invention;

FIG. 7 is a graph showing relationship between voltage and pH in aniron-water system, calculated by saturated solubility 0.065 g/100 g inatmospheric saturated water at 25° C. of iron(II) carbonate—ironconcentration of water 5.6×10−3 mol/L;

FIG. 8 is a schematic diagram of a partial system of a characteristicportion of another embodiment of a film forming apparatus according tothe present invention;

FIG. 9 is a schematic diagram of a partial system of a characteristicportion of another embodiment of a film forming apparatus according tothe present invention;

FIG. 10 is a schematic diagram of a system of another embodiment of afilm forming apparatus according to the present invention;

FIG. 11 is a schematic diagram of a system of another embodiment of afilm forming apparatus according to the present invention;

FIG. 12 is a schematic diagram of a system of another embodiment of afilm forming apparatus according to the present invention;

FIG. 13 is a schematic diagram of a system of another embodiment of afilm forming apparatus according to the present invention;

FIG. 14 is a schematic diagram of a system of another embodiment of afilm forming apparatus according to the present invention;

FIG. 15 is a schematic diagram of a system of another embodiment of afilm forming apparatus according to the present invention;

FIG. 16 is a schematic diagram of a system of another embodiment of afilm forming apparatus according to the present invention;

FIG. 17 is a flowchart showing a procedure for performing noble metaldeposition treatment after forming of a ferrite film according to thepresent invention; and

FIG. 18 is a flowchart showing another procedure for performing noblemetal deposition treatment after forming of a ferrite film according tothe present invention.

DESCRIPTION OF EMBODIMENTS OF THE INVENTION

Hereunder, embodiments concerning a method of suppressing deposition ofradionuclides on components of a nuclear power plant according to thepresent invention will be explained, referring to the drawings.

First Embodiment

FIG. 1 shows a flowchart of an embodiment of a radionuclide depositionsuppression method of the present invention, FIG. 5 shows a schematicdiagram of a whole system construction of an embodiment in which thepresent invention is applied to recirculation piping of a nuclear powerplant, and FIG. 6 shows a schematic diagram of a detailed systemconstruction of a film forming apparatus for practicing the radionuclidedeposition suppression method according to the present invention.

As shown in FIG. 5, the nuclear power plant comprises a nuclear reactor1 having fuel rods contained in a pressure vessel, main steam piping 2connected to the top of the nuclear reactor 1, a steam turbine generator3 connected to the main steam piping 2, and a condenser 4 connected to asteam outlet of the steam turbine generator 3. The condensate condensedin the condenser 4 is taken out by a condensate pump 5, and returned asfeed water for the nuclear reactor 1 through a feed water piping systemwhich comprises a condensate purifying apparatus 6, a feed water pump 7,a low pressure feed water heater 8, and a high pressure feed waterheater 9. Heat sources of the low pressure feed water heater 8 and thehigh pressure feed water heater 9 are extraction steam from the steamturbine generator 3.

Further, a plurality of reactor-water recirculation systems are providedfor recirculating cooling water in the nuclear reactor 1, andconstructed so that the reactor water extracted by a plurality ofrecirculation pumps 21 connected to a bottom portion of the nuclearreactor 1 is returned to an upper portion of the nuclear reactor 1through reactor-water recirculation piping connected to the respectiverecirculation pumps, thereby to be recirculated. Further, areactor-water purifying system for purifying the reactor water in thenuclear reactor 1 is constructed so that the reactor water extracted bya purifying system pump 24 connected to the bottom portion of thenuclear reactor 1 is cooled through a regenerative heat exchanger 25 anda non-regenerative heat exchanger 26, and the cooled reactor water ispurified by a reactor-water purifying apparatus 27 and returned into thenuclear reactor 1 from a downstream side of the high pressure feed waterheater of the feed water piping system after rising the temperature ofthe purified reactor water by the regenerative heat exchanger 25.Further, FIG. 5 shows the case where the present invention is applied tothe reactor-water recirculation system, and the state that a ferritefilm formation apparatus 30 for practicing the radionuclide depositionsuppression method according to the present invention is connected tothe reactor-water recirculation system by temporary piping. That is,when a service operation of the nuclear reactor 1 is stopped, connectionbetween the nuclear reactor 1 and the reactor-water recirculation piping22 is cut off, and the ferrite film formation apparatus 30 is connectedto the cut-off reactor-water recirculation system though the temporarypiping so that a processing solution can be recirculated.

An embodiment of the ferrite film formation apparatus 30 is shown inFIG. 6. The film formation apparatus 30 of the present embodiment isconstructed so that it can be jointly used with chemical decontaminationprocessing. Namely, the apparatus 30 comprises a surge tank 31 filledwith water used for processing, and a recirculation pump 32 forextracting the water in the surge tank 31 and feeding it to an end ofthe reactor-water recirculation piping 22 through valves 33, 34.Chemical tanks 42, 43 and 44 each used for chemical decontamination areconnected to a processing solution piping 35 having the valves 33 and 34connected thereto through valves 36, 37 and 38 and injection pumps 39,40 and 41. In the chemical tank 42, permanganic acid ions for oxidativedissolution of contaminated substances inside the piping are stored. Inthe chemical tank 43, oxalic acid for reductive dissolution ofcontaminated substances in the piping is stored. In the chemical tank44, hydrazine for pH adjustment is stored. Further chemical tanks 49 and50 each used for ferrite film formation are connected to the processingsolution piping 35 through valves 45 and 46 and injection pumps 47 and48. In the chemical tank 49, chemicals including iron (II) ions preparedby dissolving iron with formic acid are stored. Further, chemicals fordissolving iron are not limited to the formic acid, but organic acid orcarbonic acid, which becomes counter anion to the iron (II) ion, can beused therefor. In the chemical tank 50, water in which oxygen asoxidizing agent is dissolved is stored. Further, hydrazine stored in thechemical tank 44 is used for pH adjustment at time of ferrite filmformation.

Meanwhile, the processing solution fed to the one end of thereactor-water recirculation piping 22 by the recirculation pump 32 ispassed through an inside of the reactor-water recirculation piping 22and returned to the valve 51 from the other end. The processing solutionreturned through the valve 51 is returned to the surge tank 31 through arecirculation pump 52, a heater 53 and valves 55, 56 and 57. A cooler 58and a valve 59 are connected to the heater 53 and the valve 55 inparallel. The valve 56, a cation exchange resin tower 60 connected to avalve 61 in series and a mixed bed ion exchange resin 62 connected to avalve 63 in series are connected to the processing solution piping 35 inparallel, respectively. Decomposition equipment 64 is connected inparallel with a valve 57 via a valve 65. A chemical tank 68 is connectedto the decomposition equipment 64 via a valve and an injection pump 67,and constructed so that the hydrogen peroxide solution stored in thechemical tank 68 can be injected into the decomposition equipment 64.

It is preferable that the position of the valve 46 for oxidizerinjection is at a downstream side of the valve 45 for iron (II) ioninjection and the valve 38 for pH adjuster injection, and possibly closeto an object to be treated. Further, it is preferable to set a filter atan exit side of the surge tank 31. Further, it is preferable forremoving oxygen in solution to bubble inert gas such as nitrogen, argongas, etc. in the chemical tank storing chemicals including iron (II)ions, the chemical tank 44 storing pH adjusting chemicals, and the surgetank 31. Further, the decomposition equipment 64 is constructed so thatorganic acid used as counter anion of iron (II) ion and hydrazine of pHadjuster can be decomposed. That is, as the counter anion of iron (II)ion, organic acid which can be decomposed into water and carbon dioxidetaking into consideration of reduction in waste amount, or carbonic acidwhich can be released as gas and does not increase an amount of wastesis used. Further, it is preferable for suppressing a use amount ofchemicals to recover unreacted chemicals by separating and removingexcessive reaction products and reuse them.

Using the film formation apparatus 30 constructed as mentioned above, aprocessing procedure for practicing the radionuclide depositionsuppression method according to the present invention in thereactor-water recirculation system will be explained along the flowchartof FIG. 1. First of all, in practice of the method of the presentinvention, it starts from connection of the film formation apparatus 30to the piping system including a component that a film is to be formed(S1). For example, as in FIG. 5, in the case where the reactor-waterrecirculation system is to be treated, connection of the nuclear reactor1 and the reactor-water recirculation piping 22 is cut off, and the filmformation apparatus 30 is connected to the cut-off reactor-waterrecirculation system through temporary piping.

Next, in the present embodiment, contaminated substances such as oxidefilms taken in radionuclides formed on the metal member surfaces incontact with the reactor water are decomposed by chemical processing,using the film formation apparatus 30 (S2). When the radionuclidedeposition suppression method of the present invention is practiced, itis preferable to conduct the chemical processing, however, it is notlimited to the chemical processing. It is necessary that the metalmember surface or surfaces are exposed before practicing theradionuclide deposition suppression method, and it is possible to employmechanical decontamination such as grinding.

The chemical decontamination in step S2 is a conventional method,however, it will be explained briefly. First, the valves 33, 34, 51, 55,56 and 57 are opened, under the condition that the other valves areclosed, the recirculation pumps 32 and 51 are started, and theprocessing solution in the surge tank 31 is recirculated into thereactor-water recirculation system 22 that is to be chemicallydecontaminated. Further, the temperature of the processing solution israised to a temperature of about 90° C. by the heater 53. Next, thevalve 36 is opened and the injection pump 39 is started, permanganicacid ions in the chemical tank 42 is injected into the processingsolution. Thereby, radioactive contaminant such as oxide films formed onthe object that is to be decontaminated is oxidatively dissolved.

After the oxidative dissolution of radioactive contaminant is finishedin this manner, in order to decompose permanganic acid remained in theprocessing solution, the valve 37 is opened and the injection pump 40 isstarted, and oxalic acid in the chemical tank 43 is injected into theprocessing solution. Successively, in order to conduct reductivedissolution of the contaminant, the oxalic acid in the chemical tank 43is further injected into the processing solution, and in order to adjustthe pH of the processing solution, the valve 38 is opened and theinjection pump 41 is started, and hydrazine is injected from thechemical tank 44 into the processing solution. After oxalic acid andhydrazine are injected in this manner, the valve 61 is opened and thevalve 56 is closed, the processing solution is passed to the cationexchange resin tower 60, the metal cation dissolved into the processingsolution is adsorbed on the cation exchange resin and removed from theprocessing solution.

After, the reductive dissolution is finished, in order to decompose theoxalic acid in the processing solution, the opening of the valve 57 forbypassing the valve 65 at the exit side of the decomposition equipment64 and the decomposition equipment 64 is adjusted, whereby a part of theprocessing solution is flowed into the decomposition equipment 64. Atthis time, the valve 66 is opened, the injection pump 67 is started, andhydrogen peroxide in the chemical tank 68 is injected into theprocessing solution flowing into the decomposition equipment 64, wherebythe oxalic acid is decomposed in the decomposition equipment 64. Afterthe oxalic acid is decomposed, in order to remove the impurities in theprocessing solution, the heater is turned off and the valve 55 isclosed. At the same time, the valve 59 of the cooler 58 is opened andthe processing solution is passed into the cooler 58 to be lowered intemperature. After the temperature of the processing solution is loweredto a temperature (for example 60° C.) at which it can be passed thoughthe mixed bed resin tower 62 in this manner, the valve 61 of the cationexchange resin tower 60 is closed and the valve 63 at the side of themixed bed resin exchange tower 62 is opened, and the processing solutionis flowed into the mixed bed ion exchange tower 62, thereby to removeimpurities in the processing solution.

Those series of operations from temperature elevation, oxidizerdissolution, oxidizer decontamination, reductive dissolution, reductivedecomposition and purifying operation are repeated twice or thrice,whereby contaminants including oxide films of the metal member that isto be decontaminated are dissolved and removed.

In this manner, after the contaminants including oxide films of themetal members are removed, the processing is changed to a ferrite filmforming processing according to the present invention. First, afterfinishing of the final purification operation, the processing solutionis adjusted to be a prescribed temperature by the heater 53 (S3). Theprescribed temperature at this time is preferable to be around 100° C.,however, it is not limited to the temperature. The point is that theformed ferrite film is sufficiently dense in film structure such ascrystal to the extent that radionuclides in the reactor water duringservice operation of the nuclear reactor cannot be taken in. Therefore,at least, 200° C. or lower is preferable and although the lower limit issufficient to be a normal temperature, 60° C. or higher at which aforming rate of the film becomes in a practical range is preferable.

Further, from a view point of suppression of a use amount of chemicalsalso, the temperature of the processing solution for forming a ferritefilm is preferable to be 60-100° C. The reason is explained. FIG. 7shows relationship between voltage and pH in an iron-water system,calculated by saturated solubility 0.065 g/100 g in atmosphericsaturated water at 25° C. of iron(II) carbonate−iron concentration ofwater 5.6×10−3 mol/L. From FIG. 7, it is found that a stabilized regionof magnetite (Fe3O4) which is a kind of ferrite is expanding to a low pHside as the temperature rises from 25° C. to 60° C., and from 60° C. to100° C. Therefore, it is possible to reduce an amount of chemical foradjusting the pH of the processing solution by raising the temperature.In order to form a ferrite film, it is necessary that iron (II) ion isadsorbed on the surface of an object that a film is to be formed.However, iron (II) ion in the solution is oxidized to iron (III) ion bydissolved oxygen according to the following chemical formula 1, the iron(III) ion is precipitated as iron hydroxide according to the followingchemical formula 2 because the iron (III) ion is lower in solubilitythan iron (II) ion, so that the iron (III) ion comes not to contributeto ferrite film formation. Therefore, it is preferable to conductbubbling of inert gas or vacuum deaeration in order to remove oxygen inthe processing solution.

4Fe2++O2+2H2O→4Fe3++4OH—  (1)

Fe3++3OH—→Fe(OH)3  (2)

When the temperature of the processing solution recirculated in thismanner reaches a prescribed temperature, the valve 45 is opened and theinjection pump 47 is started, chemicals containing iron (II) ionprepared by dissolving and adjusting iron by formic acid are injectedinto the processing solution from the chemical tank 49 (S4). Thereby,the iron (II) ion is adsorbed on the metal member surface that is to betreated. Successively, in order to oxidize the iron (II) ion adsorbed onthe metal member surface to be iron (III) ion and to make it intoferrite, the valve 46 is opened and the injection pump 48 is started,whereby water having oxygen of oxidizer dissolved therein and stored inthe chemical tank 50 is injected into the processing solution (S5).Successively, in order to adjust the pH of the processing solution to5.5-9.0, the valve 38 is opened and the injection pump 41 is started,and hydrazine is injected from the chemical tank 44 into the processingsolution (S6). Thereby, an oxide film of ferrite film (hereunder,referred to as magnetite film) that magnetite is a main component isformed on the position of an object to be treated.

In step S7, when formation of the magnetite film is finished in thismanner, the processing goes to a waste solution processing step S8.However, when the magnetite film formation is not finished, theprocessing goes to step S9 where chemicals are filled, and then amagnetite film of necessary thickness is formed.

Since formic acid and hydrazine remain in the processing solution afterforming of the magnetite film, it is necessary to have removed theseimpurities by practicing the waste liquid treatment in step S8 when thewaste solution is discharged. Meanwhile, disposal of those impurities inthe ion exchange resin tower 60 increases waste of the ion exchangeresin. Therefore, in the waste liquid treatment in step S8, it ispreferable to decompose and dispose the formic acid to carbon dioxideand water, and the hydrazine into nitrogen and water, using thedecomposition equipment 64 in the decontamination system. Thereby, it ispossible to reduce a load of the ion exchange resin tower 60 and toreduce a waste amount of the ion exchange resin. Further, since thedecomposing disposal causes a part of the processing solution to flow inthe decomposition equipment as in the decomposition of oxalic acid,formic acid and hydrazine are decomposed by adjusting the openings ofthe valve 57 bypassing the decomposition equipment 64 and the valve 65of the decomposition equipment 64, and injecting hydrogen peroxide intothe processing solution flowing in the decomposition equipment 64. Inthis manner, by forming the magnetite film on the object to be treatedwhile suppressing the waste of ion exchange resin and a generationamount of radioactive waste, it is possible to suppress deposition ofradionuclides or radioactive cobalt ions on the object to be treatedduring normal service operation of the nuclear reactor. As a result, itis possible to reduce exposure at time of regular inspection bysuppressing a dose rate of the piping of the reactor-water recirculationsystem.

Further, chemicals such as chlorine are not used for the film formationprocessing, so that the soundness of components of the nuclear powerplant is not spoiled.

Second Embodiment

FIG. 8 shows a system of a concrete embodiment of a portion forming iron(II) ions stored in the chemical tank 49 shown in FIG. 6. In FIG. 8,formic acid solution is stored in a chemical tank 70, and nitrogen fromnitrogen bubbling equipment 71 is bubbled in the chemical tank 70,whereby dissolved oxygen is removed. The formic acid from which thedissolved oxygen is removed is transferred to a metal iron dissolutiontank 73 by an injection pump 72. Metal iron 74 is set in the metal irondissolution tank 73, and iron (II) ion is dissolved by the formic acidtransferred thereto. At this time, nitrogen from the nitrogen bubblingequipment 71 is bubbled in the metal iron dissolution tank 73. Theformic acid solution in the metal iron dissolution tank 73 does notsubstantially include dissolved oxygen, so that the iron (II) ion isalmost not oxidized to iron (III) ion. The formic acid solution whichdissolved the iron (II) ion is transferred to the chemical tank 49 by aninjection pump 75 and stored therein. Further, nitrogen from thenitrogen bubbling equipment 71 is bubbled in the chemical tank 49.Nitrogen from the nitrogen bubbling equipment 71 is bubbled also duringstorage, and prevents the iron (II) ion from being oxidized to Iron(III) ion by oxygen in the air.

The iron (II) ion solution formed and stored in this manner is used forthe film formation processing of the first embodiment shown in FIG. 6.Therefore, the iron (II) ion solution prepared according to theembodiment of FIG. 8 is not in contact with oxidizer until the solutionis mixed with the oxidizer such as oxygen to be injected from thechemical tank 50 in the film formation apparatus 30, so that an amountof the iron (II) ion as it is becomes much. Therefore, the amount ofiron (II) ion adsorbed on the object portion to be treated increases andthe formation reaction of magnetite film becomes easy to occur.

Third Embodiment

FIG. 9 shows a system of another embodiment of iron (II) ion formationshown in FIG. 8. In the present embodiment, carbonic water instead offormic acid in the embodiment of FIG. 8 is used as an iron ion solution.Carbonic acid is stored in a chemical tank 76, carbon dioxide suppliedform a carbon dioxide bubbling equipment 77 is bubbled into the chemicaltank 76, and saturated carbonic water of one atmosphere is formed. Theformed one atmosphere saturated carbonic water is transferred to themetal iron dissolution tank 73 by the injection pump 72. Iron (II)carbonate 78 is contained in the metal iron dissolution tank 73, and theone atmosphere saturated carbonic water is dissolved. Further, carbondioxide from the carbon dioxide bubbling equipment 71 is bubbled intothe metal ion dissolution tank 73. By the way, according to theliterature (Chemical Unabridged Dictionary 5, page 729 (1997),Reduced-size edition), usually, the solubility of iron (II) carbonate is0.065 g/100 g-water at 20° C., however, in the case of one atmospheresaturated carbonic water, the solubility rises to 0.1 g/100 g-water.Further, it can exhaust dissolved oxygen and does not substantiallycontain dissolved oxygen, so that the dissolve iron (II) ion is almostnot oxidized to iron (III) ion. The saturated carbonic water solution inwhich iron (II) ion is dissolved is transferred to and stored in thechemical tank 49 by the injection pump 75 via a filter 79 removingundissolved iron (II) ion. During storage, also, carbon dioxide fromcarbon dioxide bubbling equipment 77 is bubbled into the chemical tank49, whereby the iron (II) ion is prevented from being oxidized to beiron (III) ion by oxygen in the air.

The iron (II) ion solution produced and stored in this manner is usedfor the film formation processing shown in FIG. 6. Since the iron (II)ion solution prepared in the embodiment shown in FIG. 9 does not contactwith oxidizer until it is mixed with the oxidizer such as oxygeninjected from the chemical tank 50 in the film formation apparatus 30,an amount of iron (II) ion as it is and reached to an object portion tobe treated becomes much. Therefore, an amount of iron (II) ion adsorbedon the object portion to be treated increases, and the reaction ofmagnetite film production becomes easy to occur. Further, since carbonicacid ion is used as counter anion of iron (II) ion, it is possible toreduce an amount of solid waste.

Fourth Embodiment

FIG. 10 shows a system of another embodiment of the film formationapparatus 30 according to the present invention. A difference of thepresent embodiment from the embodiment shown in FIG. 6 is that thenitrogen bubbling equipment 71 is connected to each of the surge tank31, the chemical tank 44 for hydrazine and the chemical tank for iron(II) ion. Thereby, it is possible to make each solution contained ineach tank into the solution substantially not containing oxygen byexhausting dissolved oxygen in each tank. As a result, it is possible toreduce formation of iron (III) ion contained in the solution and notdistributed to magnetite film formation and to suppress decrease inmagnetite film formation reaction, as well as the above-mentioned secondand third embodiments.

Fifth Embodiment

FIG. 11 shows a system of another embodiment of the film formationapparatus 30 according to the present invention. In the presentinvention, a filter 80 for removing side reaction products is providedbetween the recirculation pump 32 at the exit side of the surge tank 31and the valve 33, in addition to the embodiment shown in FIG. 10. In themagnetite film formation, iron (II) ion is adsorbed on an object surfaceto be treated, a part thereof is oxidized to iron (III) ion by oxidizerinjected from the chemical tank 50 to form ferrite, and it grows as afilm by repeating the adsorption and oxidization. However, in thesolution being transferred, also, iron (II) ion reacts with oxidizerinjected from the chemical tank 50, and a part thereof becomes iron(III) ion and turns into ferrite particles and iron (III) (ferric)hydroxide particles in the solution. Since those particles grow as timepasses, they are easy to grow inside the surge tank 31 in which theystay for a long time. When the grown those particles are supplied againto the object portion that a film is to be formed, there is thepossibility that they are taken in the magnetite film which is growingand uniform growth of the magnetite film is spoiled. Particularly, whenion (III) hydroxide is taken in, in some cases, radioactive cobalt istaken in when hematite is produced by dehydration reaction.

In order to make the magnetite film grow uniformly on the object portionsurface, it is preferable to remove particle-shaped products grown byside reaction, and it is effective to install a filter 80 for removingside reaction products at the exit side of the surge tank 31 in whichthe particle-shaped products are easy to grow. Thereby, an amount ofparticle-shaped products grown by side reaction to the object portion tobe treated decreases and the magnetite film easily grows uniformly.

Sixth Embodiment

FIG. 12 shows a system of another embodiment of the film formationapparatus 30 according to the present invention. The present embodimentis a concrete example in which oxygen saturated water is formed asoxidizer which is stored in the chemical tank 50, in addition to theembodiment shown in FIG. 11. As shown in FIG. 12, water is filled in thechemical tank 50, and while recirculating the water by a recirculationpump 81, oxygen-containing gas is injected into the recirculating waterfrom oxygen-containing gas injection equipment 82, whereby oxygensaturated water at the oxygen concentration of the oxygen-containing gasis formed. The oxygen saturated water is used as oxidizer for magnetitefilm formation. Thereby, waste does not occur from the oxidizer, and itis possible to reduce an amount of waste by the amount corresponding tothe waste that does not occur from the oxidizer.

Seventh Embodiment

FIG. 13 shows a system of further another embodiment of the filmformation apparatus 30 according to the present invention. In thepresent embodiment, oxygen-containing gas is supplied to micro-bubblegeneration equipment 83 from the oxygen-containing gas injectionequipment 82 and oxygen-containing gas micro-bubble is injected into theprocessing solution piping 35 from the micro-bubble generation equipment83, instead of the chemical tank for oxidizer in FIG. 6. Themicro-bubble generation equipment 83 is provided on branch pipingbranched from the processing solution piping 35 to supply a part ofprocessing solution supplied to the object portion to generatemicro-bubble, and the branched piping is formed so that the part ofprocessing solution is mixed with the oxygen-containing gas suppliedfrom the oxygen-containing gas injection equipment 82 at the branchedpiping, generates oxygen-containing gas bubble, and is returned to theprocessing solution piping 35. The air bubble micro-bubbled is very slowin rising velocity in liquid phase, so that it is not separated sooninto gas and liquid phases as in usual air bubble, and the air bubble asit is flows along the liquid phase in the field that flow exists.Therefore, according to the present embodiment, the oxidizer reaches theobject portion to be treated as micro-bubble of oxygen-containing gas.

Further, according to the present embodiment, since the oxygen containedin the micro-bubble does not react directly with iron (II) ion in liquidphase because the oxidizer of micro-bubble is used, it is possible toreduce an amount of iron (II) ion oxidized to iron (III) ion in liquidphase before reaching to the object portion to be treated, as comparedwith the sixth embodiment.

Eighth Embodiment

FIG. 14 shows a system of further another embodiment of the filmformation apparatus 30 according to the present invention. In thepresent embodiment, in addition to the embodiment shown in FIG. 13,ascorbic acid injection equipment is provided. The ascorbic acidinjection equipment is constructed so that ascorbic acid solution isinjected into the processing solution piping 35 from a chemical tank 84storing ascorbic acid solution via a pump 85 and the valve 86. Theascorbic acid solution in the chemical tank 84 is bubbled by nitrogenfrom the nitrogen bubbling equipment 71, and dissolved oxygen is removedtherefrom. The ascorbic acid injected in the processing solution piping35 is mixed with processing solution containing bubble ofoxygen-containing gas reaches to the object surface to be treatedtogether with iron (II) ion and pH adjuster. Meanwhile, a part of iron(II) ion has oxidized to iron (III) ion by a part of dissolved oxygendissolved in liquid from micro-bubble of oxygen-containing gas. However,according to the present embodiment, ascorbic acid exists, so that iron(III) ion is reduced to the iron (II) ion, and it is possible to reducea consumption amount of iron (II) ion. In this manner, most of theinjected iron (II) ion as it is reaches to the object surface to betreated and adsorbed. A part of the adsorbed iron (II) ion is oxidizedby oxygen contained in micro-bubble, and causes ferrite forming reactiontogether with iron (II) ion adsorbed without being oxidized to formmagnetite film.

Therefore, it is possible to form a magnetite film by using a chemicalcontaining at least one of iron (II) ion and iron (III) ion instead ofiron (II) ion in the present embodiment, and contacting the processingsolution formed by mixing ascorbic acid as a reducer reducing iron (III)ion and a chemical adjusting the pH of the processing solution to 5.5 to9.0 with a metal member surface.

Ninth Embodiment

FIG. 15 shows a system of further another embodiment of the filmformation apparatus 30 according to the present invention. In thepresent embodiment, ultraviolet irradiation equipment 87 is used insteadof the dissolution equipment 64 in FIG. 6. As in the first embodiment,in order to decompose formic acid and hydrazine after finishing ofmagnetite film formation, openings of the valve 57 and the valve 65 ofthe ultraviolet irradiation equipment 87 are adjusted, and a part of theprocessing solution is flowed into the ultraviolet irradiation equipment87. At the same time, the valve is opened and the injection pump 67 isstarted, and the hydrogen peroxide in the chemical tank 68 is injectedinto the ultraviolet irradiation equipment 87. Thereby, a part of thehydrogen peroxide received ultraviolet irradiation produces OH radical,and the OH radical conducts oxidative decomposition of formic acid andhydrazine into carbon dioxide and water, and into nitrogen and water,respectively. As a result, it is possible to decompose the chemicalcontained in a waste solution after finishing magnetite film formationand to reduce a waste amount.

Tenth Embodiment

FIG. 16 shows a system of further another embodiment of the filmformation apparatus 30 according to the present invention. The presentembodiment is characterized in that micro-bubble generation equipment 89is used instead of the decomposition equipment 64 in the embodimentshown in FIG. 6. As shown in FIG. 16, the present embodiment isconstructed so that ozone gas is blown in the micro-bubble generationequipment 89 from ozone gas supply equipment 90. As in the decompositionequipment 64, openings of the valve 57 and the valve 65 at the exit sideof the micro-bubble generation equipment 89 are adjusted, whereby a partof the processing solution in the micro-bubble generation equipment 89is passed through. Thereby, the ozone gas blown in the micro-bubblegeneration equipment 89 becomes ozone micro-bubble in the processingsolution containing formic acid and hydrazine. The ozone dissolved inthe processing solution directly decomposes oxidatively formic acid andhydrazine or formic acid and hydrazine are oxidatively decomposed by OHradical generated by a reaction of ozone and water to becomes carbondioxide, nitrogen and water. Thereby, a waste amount is reduced bydecomposing chemicals contained in the waste after finishing ofmagnetite film formation to gas and water.

Eleventh Embodiment

Further another embodiment according to the present invention will bedescribed, referring to FIG. 17. FIG. 17 shows a flowchart showing aprocedure for performing noble metal deposition treatment which isusually not conducted immediately after chemical decontamination. Thenoble metal deposition treatment is conducted for suppressing stresscorrosion cracking of components of a nuclear reactor. Usually it isconducted using about 48 hours when the temperature of reactor waterreaches to 150° C. from a starting time of stopping operation in timewhen the nuclear reactor is going to be stopped or intermediatelystopped to a time when the nuclear reactor is stopped. The reason thatthe treatment is not conducted immediately after chemicaldecontamination is that noble metal is difficult to deposit on thenuclear reactor component surface from which an oxide film is removed bythe chemical decontamination. The noble metal deposition treatment isconducted after an oxide film grows to some extent. The reason that itis conducted at 150° C. is that the efficiency to deposition is best asa result of studying of a noble metal deposition amount under varioustemperature conditions.

Namely, as shown in FIG. 17, magnetite film formation processing isconducted (S12) immediately after chemical decontamination (S11). Next,temperature elevation of the nuclear reactor is started (S13, S14) atthe same time as an regular inspection terminates. After the temperatureof reactor water is kept at 150° C. for 48 hours (S15), noble metal isinjected (S16), and then temperature elevation of the nuclear reactor isrestarted (S17) and the operation is shifted to the rated operation(S18).

In this manner, according to the present embodiment, the magnetite filmof metal oxide is formed on the object surface to be treated by themagnetite film processing immediately after the chemicaldecontamination, so that a noble metal element is easy to be depositedby the noble metal deposition treatment. When the temperature of reactorwater reaches to 150° C. from starting of the nuclear reactor, injectionof a noble metal compound including platinum and rhodium is started andthe condition is kept for about 48 hours, whereby it is possible toconduct the noble metal deposition treatment.

Twelfth Embodiment

FIG. 18 shows a flowchart showing another procedure for performing noblemetal deposition treatment. In the present embodiment, after magnetitefilm processing is finished, immediately, a noble metal depositiontreatment is conducted by using the film formation apparatus 30 as itis. As noble metal injection equipment, the oxalic acid injectionequipment as shown in FIG. 6, for instance can be used. That is, asolution of a noble metal compound containing platinum and rhodium iscontained into the chemical tank 43, and the solution is injected intothe processing solution by using the injection pump 40. The temperaturerises only to about 100° C., however, since no nuclear fuel is containedin the processing solution, it is unnecessary to worry about influenceon zircalloy, so that it is possible to raise the concentration higherthan the usual noble metal deposition treatment and extend the treatmenttime, whereby it is possible to deposit noble metal of a prescribedamount.

Namely, as shown in FIG. 18, after chemical decontamination is conducted(S21), immediately, film formation processing of magnetite film isconducted (S22), successively, noble metal deposition treatment isconducted (S23), then elevation of the temperature of the nuclearreactor is started at the same time as the regular inspection finishes(S24, S25) and the nuclear reactor operation is shifted to the ratedoperation (S18).

1. A method of suppressing deposition of radionuclides on components ofa nuclear power plant, comprising the steps of: supplying a first liquidinto piping of the nuclear power plant through a pipe having a pump forpressurizing the first liquid and a heating apparatus for heating thefirst liquid after the nuclear power plant is stopped and beforestarting the nuclear power plant, wherein the first liquid: includesiron (II) ions, organic acid that dissolves iron for preparing the iron(II) ions, chemical for oxidizing the iron (II) ions to iron (III) ions,and chemical for adjusting pH of the first liquid; and is adjusted to atemperature within 60° C. to 100° C. by the heating apparatus; adsorbingthe iron (II) ions on a surface of a metal member composing the pipingafter the stop of the nuclear power plant and before the start of thenuclear power plant; forming a ferrite film on the surface of the metalmember by oxidizing the adsorbed iron (II) ions at a temperature within60° C. to 100° C. after the stop of the nuclear power plant and beforethe start of the nuclear power plant; suppressing deposition of theradionuclides on the metal member by the ferrite film; and decomposingthe organic acid and the chemical for adjusting pH into gas and waterafter formation of the ferrite film is finished.
 2. A method ofsuppressing deposition of radionuclides on components of a nuclear powerplant according to claim 1, wherein the film formation processing of aferrite film is conducted after removing contaminants including an oxidefilm deposited on the metal member surface.
 3. A method of suppressingdeposition of radionuclides on components of a nuclear power plantaccording to claim 1, further comprising the step of: connecting thepipe to the piping after the stop of the nuclear power plant and beforethe start of the nuclear power plant, wherein the supply of the firstliquid is carried out after connecting the pipe to the piping.
 4. Amethod of suppressing deposition of radionuclides on components of anuclear power plant comprising the steps of: supplying a processingsolution into piping of the nuclear power plant through a pipe having apump for pressurizing the processing solution and a heating apparatusfor heating the processing solution after the nuclear power plant isstopped and before starting the nuclear power plant, wherein theprocessing solution: includes a first chemical including iron (II) ionsand organic acid that dissolves iron for preparing the iron (II) ions, asecond chemical for oxidizing the iron (II) ions to iron (III) ions, anda third chemical for adjusting the pH of the processing solution, isadjusted to a temperature within 60° C. to 100° C. by the heatingapparatus, and has a pH adjusted within 5.5 to 9.0, wherein the first,second and third chemicals are individually supplied to the pipe;forming a ferrite film on the surface of the metal member after the stopof the nuclear power plant and before the start of the nuclear powerplant by contacting the processing solution with a surface of a metalmember composing the piping at a temperature within 60° C. to 100° C.;suppressing deposition of radionuclides on the metal member by theferrite film; and decomposing the organic acid and the chemical foradjusting pH into gas and water after formation of the ferrite film isfinished.
 5. A method of suppressing deposition of radionuclides oncomponents of a nuclear power plant according to claim 4, wherein thefirst chemical is a solution in which metal iron is dissolved in organicacid.
 6. A method of suppressing deposition of radionuclides oncomponents of a nuclear power plant according to claim 5, wherein thefirst chemical is prepared by dissolving the metal iron in the solutioncontaining organic acid to iron (II) ions after bubbling by inert gas orvacuum deaeration of said solution.
 7. A method of suppressingdeposition of radionuclides on components of a nuclear power plantaccording to claim 4, wherein the first chemical is a solution in whichiron carbonate is dissolved in carbonic water or organic acid.
 8. Amethod of suppressing deposition of radionuclides on components of anuclear power plant according to claim 4, wherein inert gas is bubbledin at least one of a tank storing the first chemical, a tank storing thethird chemical and a surge tank storing the processing solution.
 9. Amethod of suppressing deposition of radionuclides on components of anuclear power plant according to claim 1, wherein the ferrite film is amagnetite film.
 10. A method of suppressing deposition of radionuclideson components of a nuclear power plant according to claim 1, wherein theadsorption of the iron (II) ions onto the surface of the metal membertakes place by contacting a processing solution containing the iron (II)ions with the surface.
 11. A method of suppressing deposition ofradionuclides on components of a nuclear power plant according to claim10, wherein the iron (II) ions are added to the processing solution. 12.A method of suppressing deposition of radionuclides on components of anuclear power plant according to claim 4, wherein the ferrite film is amagnetite film.
 13. A method of suppressing deposition of radionuclideson components of a nuclear power plant according to claim 4, wherein theprocessing solution include the first, second and third chemicals isheated at a temperature of from 60° C. to 100° C.
 14. A method ofsuppressing deposition of radionuclides on components of a nuclear powerplant according to claim 2, wherein a circulation loop for circulatingthe first liquid is formed by using the pipe and the piping.
 15. Amethod of suppressing deposition of radionuclides on components of anuclear power plant according to claim 2, wherein the process forremoving the contaminants is conducted by supplying a second liquid forconducting chemical decontamination through the pipe; and the processfor supplying the first liquid is conducted after removing thecontaminants.
 16. A method of suppressing deposition of radionuclides oncomponents of a nuclear power plant according to claim 15, wherein thechemical decontamination repeats oxidative removing and reductiveremoving.
 17. A method of suppressing deposition of radionuclides oncomponents of a nuclear power plant according to claim 4, wherein acirculation loop for circulating the first liquid is formed by using thepipe and the piping.
 18. A method of suppressing deposition ofradionuclides on components of a nuclear power plant according to claim4, further comprising the step of: conducting chemical decontaminationincluding an oxide film deposited on the metal member surface bysupplying liquid for conducting chemical decontamination through thepipe.
 19. A method of suppressing deposition of radionuclides oncomponents of a nuclear power plant according to claim 18, wherein thechemical decontamination repeats oxidative removing and reductiveremoving.
 20. A method of suppressing deposition of radionuclides oncomponents of a nuclear power plant according to claim 4, furthercomprising the step of: connecting the pipe to the piping after the stopof the nuclear power plant and before the start of the nuclear powerplant, wherein the supply of the first liquid is carried out afterconnecting the pipe to the piping.
 21. A method of suppressingdeposition of radionuclides on components of a nuclear power plantaccording to claim 4, wherein the film formation processing of a ferritefilm is conducted after removing contaminants including an oxide filmdeposited on the metal member surface.
 22. A method of suppressingdeposition of radionuclides on components of a nuclear power plant,comprising the steps of: forming a ferrite film on a surface of a metalmember composing the nuclear power plant by using a first chemicalincluding iron (II) ions and organic acid that dissolves iron forpreparing the iron (II) ion, a second chemical for oxidizing the iron(II) ions to iron (III) ions, and a third chemical for adjusting the pHof the processing solution; and decomposing the organic acid and thethird chemical for adjusting pH included in a waste liquid into gas andwater after forming the ferrite film on the surface of the metal member.23. A method of suppressing deposition of radionuclides on components ofa nuclear power plant according to claim 22, wherein decomposition ofthe organic acid and the third chemical for adjusting pH is carried outwith decomposition equipment.
 24. A method of suppressing deposition ofradionuclides on components of a nuclear power plant according to claim22, further comprising the steps of: removing contaminants including anoxide film deposited on the surface of the metal member by chemicaldecontamination; decomposing reducing agent used in reductive removingincluded in the chemical decontamination after the reductive removing;and carrying out formation of the ferrite film after decomposition ofthe reducing agent.
 25. A method of suppressing deposition ofradionuclides on components of a nuclear power plant according to claim24, wherein decomposition of the organic acid and the third chemical foradjusting pH is carried out with decomposition equipment used in thedecomposition of the reducing agent.
 26. A method of suppressingdeposition of radionuclides on components of a nuclear power plantaccording to claim 22, wherein the organic acid is formic acid.
 27. Amethod of suppressing deposition of radionuclides on components of anuclear power plant according to claim 22, further, comprising the stepsof: removing contaminants including an oxide film deposited on thesurface of the metal member by chemical decontamination; decomposingreducing agent and a second pH adjusting agent used in reductiveremoving included in the chemical decontamination after the reductiveremoving; and carrying out formation of the ferrite film afterdecomposition of the reducing agent and the second pH adjusting agent.28. A method of suppressing deposition of radionuclides on components ofa nuclear power plant according to claim 27, wherein decomposition of afirst pH adjusting agent that is the third chemical and the organic acidis carried out with decomposition equipment used in the decomposition ofthe reducing agent and the second pH adjusting agent.
 29. A method ofsuppressing deposition of radionuclides on components of a nuclear powerplant according to claim 28, wherein when the first pH adjusting agentand the organic acid are decomposed and when the reducing agent and thesecond pH adjusting agent are decomposed, oxidizer is supplied into thedecomposition equipment.
 30. A method of suppressing deposition ofradionuclides on components of a nuclear power plant, comprising thesteps of: forming a ferrite film on a surface of a metal membercomposing the nuclear power plant with solution including iron (II) ion,oxidizer for oxidizing the iron (II) ion to iron (III) ion, and a firstpH adjusting agent; and decomposing the first pH adjusting agent afterforming the ferrite film on the surface of the metal.
 31. A method ofsuppressing deposition of radionuclides on components of a nuclear powerplant according to claim 30, wherein decomposition of the first pHadjusting agent is carried out with decomposition equipment.
 32. Amethod of suppressing deposition of radionuclides on components of anuclear power plant according to claim 30, wherein when the solutionincludes organic acid which dissolves iron for preparing iron (II) ion,the organic acid is decomposed after formation of the ferrite film. 33.A method of suppressing deposition of radionuclides on components of anuclear power plant according to claim 32, wherein decomposition of thefirst pH adjusting agent and the organic acid is carried out withdecomposition equipment.
 34. A method of suppressing deposition ofradionuclides on components of a nuclear power plant according to claim30, further comprising the steps of: removing contaminants including anoxide film deposited on the surface of the metal member by chemicaldecontamination; decomposing reducing agent and a second pH adjustingagent used in reductive removing included in the chemicaldecontamination after the reductive removing; and carrying out formationof the ferrite film after decomposition of the reducing agent and thesecond pH adjusting agent.
 35. A method of suppressing deposition ofradionuclides on components of a nuclear power plant according to claim34, wherein decomposition of the first pH adjusting agent is carried outwith decomposition equipment used in the decomposition of the reducingagent and the second pH adjusting agent.